ML18338A067
| ML18338A067 | |
| Person / Time | |
|---|---|
| Issue date: | 12/11/2018 |
| From: | Billone M, Haile Lindsay NRC/NMSS/DSFM/IOB, US Dept of Energy, Office of Nuclear Energy |
| To: | |
| Lindsay H | |
| Shared Package | |
| ML18338A059 | List:
|
| References | |
| Download: ML18338A067 (16) | |
Text
Sister Rod Destructive Examination Test Plans: Phase 1REG CON 2018NRC Headquarters Dec. 11, 2018M.C. Billone energy.gov/ne 2*DEMO CASK: SAFE STORAGE OF HIGH
-BURNUP FUEL
-TN-32B cask loaded with 32 PWR fuel assemblies irradiated to high burnup in North Anna reactors
- Zircaloy-4 (Zr-1.5wt.%Sn), Low
-Sn Zircaloy
-4 (Zr-1.3 wt.%Sn)*ZIRLO(Zr-1wt.%Sn-1wt.%Nb), M5 (Zr-1wt.%Nb) -Cask has been monitored during dryingand transfer to storage pad
- May be opened in 10 years for visual examination & characterization
- 25 SISTER RODS
-Extracted from DEMO Cask assemblies or from similar assemblies
-2 Zry-4, 2 LT Zry
-4, 12 ZIRLO and 9 M5GWd/MTU-ORNL completed non
-destructive examinations on all 25 rods
-10 rods were shipped to PNNL-One-half rod-equivalent of defueled cladding will be shipped to ANLBackground on Sister Rods energy.gov/ne 3*SCOPE OF ORNL NDE
-Detailed visual examinations and imaging
-Gamma scans
- Burnup profile
- Pellet-pellet interfaces and gaps
- grid spacer locations
-Eddy current measurements: lift-off (oxide
& CRUD thickness)
-Lengths and outer diameters (profile) of fuel rods
-Surface temperatures
- ORNL NDE Documentation
-Montgomery et al., Sister Rod Nondestructive Examination Final Report, SFWD-SFWST-2917-000003 Rev. 1, May 16, 2018*Destructive Examinations (DEs)
-Plans for Phase 1; DE progress to date (ORNL presentation)Non-Destructive Examinations (NDEs) and DEs energy.gov/ne 4*CHARACTERIZATION AND MATERIAL PROPERITES
-Generate data that can be compared to 10
-year stored fuel rods
- Data for as-irradiated sister rods should be sufficient as baseline for DEMO rods because of low cladding temperatures (<250 o C) for DEMO rods
-Generate data for cladding mechanical properties
- Baseline data for as
-irradiated claddingat room temperature (RT) & 200 o C *Data for heat
-treated cladding (400 o) at RT &
200 o C*DETERMINE: IS EMBRITTLEMENT DUE TO RADIAL HYDRIDES AN ISSUE?
-Heat-treat at 400 oC (DSFM-wppmH in solution) using actual rod internal pressures (RIPs) at oC)-Peak RIP and cladding hoop stress @ 400 oC are reasonable limits
-Cool at oC/h with decreasing RIP and hoop stress
-Use burst tests and ring compression tests to assess effects
-Note: RIP will be measured at oC for 18 fuel rods in Phase 1Phase 1 Test Plan Objective for Sister Rods energy.gov/ne 5 energy.gov/ne 6Hydride Orientation in Irradiated ZIRLOCladding 320+/-30 wppm 320+/-30 wppm 650+/-180 wppm 650+/-180 wppm energy.gov/ne 7Radial Hydrides in Irradiated ZIRLO following Cooling from 400 o C Peak Cladding Temperature 88 MPa 480 wppmcladding wall energy.gov/ne 8*Radial-Hydride-Induced Degradation
-DEMO Cask fuel rods
- Peak cladding temperature (PCT) <250 oC; <44 wppmH in solution
- Internal gas pressure <9 MPa; peak hoop stress <68 MPa
- Do not anticipate to observe radial
-hydride-induced degradation
-Sister Rods
- PCT = 400 owppmH; pressure <11.3 MPa; hoop stress <87 MPa
- Expect to observe radial hydrides
- Do not expect to observe radial
-hydride-induced degradation
- Anticipated Range of Peak Cladding Hoop Stresses
-FRAPCON predictions for 400 oC PCT and temperature profile
- <54 MPa for standard PWR rods; <89 MPa for IFBA rods with internal B Predictions based on end
-of-life (EOL) rod internal pressure (RIP) dataPotential for Hydride Reorientation energy.gov/ne 9EOL RIP EPRI & Sister Rod Data energy.gov/ne 10*As-Irradiated Cladding
-Hydrides are primarily oriented in circumferential direction
-Short isolated radial hydrides have been observed in cladding (ZIRLOand M5) from PWR fuel rods irradiated to high burnup
- Conditions for SignificantRadial Hydride Precipitation
-High enough (>60 wppm) hydrogen content and peak cladding temperature (PCT >285 oC)-High enough (>10 MPa) internal pressure at PCT
-High enough (>80 MPa)hoop stress @ PCT*ANL Results for ZIRLO Following 400 oC & 350 o C PCT-Radial hydride lengths and number density
-Ductility and ductility transition temperature (DTT) based on RCTsReview of Hydride
-Induced Ductility Degradation energy.gov/ne 11*ANL Cladding at 350 o C PCT-Critical stress for ZIRLOappears to be 90
+/-3 MPa-ZIRLO: test 350
-wppm-H/93-MPa, 650-wppm-H/87-MPa-ANL cladding is from lead
-test-assembly rods at >62 GWd/MTU*Sister Rod Cladding at 400 o C PCT-More prototypic linear power histories per fuel cycle (18 months)
-Wider range of hydride distributions through cladding wall
-More cladding samples available
- Allows for repeat tests and intermediate
-temperature tests
- Allows for load
-interrupt tests to better determine cladding ductility
- Offers the possibility of M5 with >100 wppmhydrogen Future Hydride
-Reorientation Testing energy.gov/ne 12AcknowledgementThisworkissupported bytheSpentFuelandWasteandScienceTechnology(SFWST)Program(NE-81),Office ofNuclearEnergy(NE-8)underContractDE-AC 02-06 CH11357.M.C. BilloneSenior Mechanical EngineerApplied Materials DivisionArgonne National Laboratory9700 S. Cass Ave., Bldg. 212Argonne, IL 60439 630-252-7146billone@anl.gov energy.gov/ne 13Questions?
energy.gov/ne 14Radial Hydrides in ZIRLO for 400 oC PCT88 MPa 480 wppm<20 oC DTT 9+/-4% RHCF 120 o C DTT 32+/-13% RHCF 20 o C DTT 20+/-10% RHCF energy.gov/ne 15Radial Hydrides in ZIRLO for 350 oC PCT 28 o CDTT 20+/-10% RHCFo CDTT 30+/-11% RHCFo CDTT 37+/-11% RHCF energy.gov/ne 16Ductility (Offset Strain) for ZIRLOvs. Test Temperature
-DTT Determination